Reactivity feedback analysis for EBR-II benchmark

Chakinis, Michael

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https://hdl.handle.net/2142/113935 Copy

Description

Title

Reactivity feedback analysis for EBR-II benchmark

Author(s)

Chakinis, Michael

Issue Date

2021-12-10

Director of Research (if dissertation) or Advisor (if thesis)

Kozlowski, Tomasz

Committee Member(s)

Munk, Madicken

Department of Study

Nuclear, Plasma, & Rad Engr

Discipline

Nuclear, Plasma, Radiolgc Engr

Degree Granting Institution

University of Illinois at Urbana-Champaign

Degree Name

M.S.

Degree Level

Thesis

Keyword(s)

• SFR
• EBR-II, reactivity feedback

Abstract

The stability of a nuclear reactor is necessary to ensure its safety. Sodium-Cooled Fast Reactors have many desirable features that make them prime candidates for the future of small modular reactor design. These include higher operating temperatures for greater efficiency and lower pressures for safer power generation. Fast reactors rely on fast neutrons from fission which allow them to extend the use of uranium and thorium, operate at higher temperatures, and increase efficiency. This work uses the System Analysis Module, SAM, as the primary simulation tool developed by Argonne National Laboratory. Although SAM’s current capabilities are primarily focused on thermohydraulic analysis, this work studies extending the capability to point kinetics for analysis of reactivity feedbacks in sodium-cooled fast reactors. Multiphysics simulations like these are necessary for safety analysis of small modular reactors. Successful application of the point kinetics model can better help the understanding of reactivity feedbacks for safety analysis. The reactivity feedback model is based around the EBR-II reactor that was operated from INL. An analysis of core radial expansion, neutron Doppler shift, and coolant density during an unprotected loss-of-flow test, SHRT45R, are shown in this work. The specific test that is being analyzed is a Shutdown Heat Removal Test that occurred at the end of EBR-II’s lifespan. The uncertainty of the results are then calculated using the University of Illinois Urbana-Champaign developed tool, the Transient Analysis PackagE, TAPE. This thesis contributes to the future of both Argonne National Laboratory’s physics code capabilities and the utilization of UIUC’s uncertainty quantification tool. It is crucial that features necessary for determining the state of a nuclear reactor can be easily and accurately monitored. A negative total reactivity can result in the safe shutdown of a nuclear reactor during an unprotected-loss-of-flow scenario.

Graduation Semester

2021-12

Type of Resource

Thesis

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http://hdl.handle.net/2142/113935

Copyright and License Information

Copyright 2021 Michael Chakinis

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